ML20211A756
| ML20211A756 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  (DPR-24-A-190, DPR-27-A-195) |
| Issue date: | 08/11/1999 |
| From: | Craig C NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20211A760 | List: |
| References | |
| NUDOCS 9908240131 | |
| Download: ML20211A756 (16) | |
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UNITED STATES p
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g NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 3DOOH001
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WISCONSIN ELECTRIC POWER COMPANY DOCKET NO, 50-266 l
POINT BEACH NUCLEAR PLANT. UNIT 1
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AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No.190 License No. DPR-24.
I 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated January 29,1999, as supplemented June 9 and July 15,1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations, D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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l 9908240131 990811 1
PDR ADOCK 05000266 P
i 2-2.
Accordingly, Facility Operating License No. DPR-27 is hereby amended to approve the removal of selected requirements from TS Section 15.6, Administrative Controls, and the relocation of other requirements to licensee-controlled documents as described in j
the licensee's application dated January 29,1999, as supplemented June 9 and July 15, 1999, and evaluated in the staff's safety evaluation attached to this amendment. This license is also hereby amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-27 is hereby amended to read as follows:
B.
Technical Soecifications j
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.195, are hereby incorporated in the license. The licensee shall operate the facility in accordance with Technical Specifications.
3.
This license amendment is effective immediately upon issuance. The Technical Specifications shall be implemented within 90 days from the date of issuance. With respect to changes to the final safety analysis report (FSAR), Wisconsin Electric Power Company shall incorporate the revisions into the next FSAR update in accordance with the schedule in 10 CFR 50.71(e).
. FOR THE NUCLEAR REGULATORY COMMISSION (LLLdL)O Gk Claudia M. Craig, Chief, Section 1 Project Directorate ill Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications i
Date of issuance: August 11, 1999 i
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.f UNITED STATES
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NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 30866 0001
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WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILIT( OPERATING LICENSE
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Amendment No.195 License No. DPR-27 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated January 29,1999, as supplemented June 9 and July 15,1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act); and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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2.
Accordingly, Facility Operating License No. DPR 24 is hereby amended to approve the removal of selected requirements from TS Section 15.6, Administrative Controls, and the relocation of other requirements to licensee-controlled documents as described in the licensee's application dated January 29,1999, as supplemented June 9 and July 15, 1999, and evaluated in the staff's safety evaluation attached to this amendment. This license is also hereby amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-24 is hereby amended to read as follows:
B.
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.190, are hereby incorporated in the license. The licensee shall operate the facility in accordance with Technical Specifications.
3.
This license amendment is effective immediately upon issuance. The Technical Specifications shall be implemented within 90 days from the date of issuance. With respect to changes to the final safety analysis report (FSAR), Wisconsin Electric Power Company shall incorporate the revisions into the next FSAR update in accordance with the schedule in 10 CFR 50.71(e).
FOR THE NUCLEAR REGULATORY COMMISSION On Claudia M. Craig, Chief, Section 1 h
Project Directorate ill Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications i
Date of issuance: August 11, 1999
ATTACHMENT TO LICENSE AMENDMENT NO.190 I
TO FACILITY OPERATING LICENSE NO. DPR-24 l
AND LICENSE AMENDMENT NO.195 TO FACILITY OPERATING LICENSE NO. DPR-27 DOCKET NOS. 50-266 AND 50-301 Revise Appendix A Technical Speedications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 15.6.1/2-1 15.6.1/2-1 l
1'.6.2-2 15.6.2-2 5
15.6.2-3 15.6.2-3 15.6.2-4 15.6.2-4 15.6.3-2 15.6.3-2 15.6.4/5-1 15.6.5-1 15.6.5-2 15.6.5-3 15.6.5-3a 15.6.6-1 15.6.6-1 15.6.8-1 15.6.8-1 15.6.8-2 15.6.8-2 15.7.8-1 15.7.8-1 15.7.8-7 15.7.8-7 i
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15.6 ADMINISTRATIVE CONTROLS 15.6.1 RESPONSIBILITY l
15.6.1.1 The Plant Manager shall be responsible for overall facility operation l
l and shall delegate in writing the succession to this responsibility during absences from the Point Beach Nuclear Plant area of greater than 48 l
hours and where ready contact by telephone or other means is not assured.
15.6.1.2 The Duty Shift Superintendent (or during his absence from the control room, the Duty Operating Supervisor) shall be responsible for the '
Control Room Command function.
15.6.2 ORGANIZATION 15.6.2.1 Onsite and offsite organizations shall be established for plant operation and corporate management, respectively.
. a.
Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or
' in equivalent forms of documentation. These requirements shall be documented in the Point Beach Nuclear Plant Final Safety
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Analysis Report, or plant procedures.
b.
The Plant Manager shall be responsible for overall' safe plant l
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operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
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Unit 1 - Amendment No.498 190 ~
-15.6.1/2-1 l
Unit 2 - Amendment No.439195
15.6 ADMINISTRATIVE CONTROLS (Continued) 15.6.2 ORGANIZATION (Continued) 15.6.2.1 (Continued) c.
The Chief Nuclear Officer shall be an officer of the Company and shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staffin operating, maintaining, and providing technical suppoit to the plant to ensure nuclear safety.
d.
The individuals who carry out health physics and quality assurance functions may report to the appropriate onsite manager, however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
FACILITY STAFF 15.6.2.2 Facility staffing shall be subject to the following requirements:
k a.
Each on-duty shift shall normally be composed of at least the l
minimum shift crew composition as follows:"
1.
Shift Superintendent (SRO)* - one per shift i
2.
Shift Technical Advisor - one per shift located on-site on ten minute call to the control room 3.
Operating Supervisor (SRO)* - one per shift
- 4.. Operator (RO)* - three per shift for one or two unit operation *"
- two per shift with neither unit in operation"*
5.
Non-licensed Operator - one per shift for each unit containing fuel and an additional one per shift when either unit is in operation ***
' Unit 1 - Amendment No.-tM 190 15.6.2-2
- Unit 2 - Amendment No.-tet 195 r
4 15.6 ADMINISTRATIVE CONTROLS (Continued) 15.6.2' ORGANIZATION (Continued)'
FACILITY STAFF (Continued) 15.6.2.2 (Continued) -
- b.
When there is fuel in either unit, an SRO* shall be in the control room at all times. In addition to this SRO*, for each unit containing fuel, an RO* or SRO* shall be present at the
- controls at all times.
c.
DELETED d.
An individual qualified in radiation protection procedures -
shall be on site when fuel is in either reactor.**
e.
All core alterations shall be directly supervised by either a
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licensed Senior Reactor Operator or Senior Reactor Operator i
Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
- SRO = NRC Senior Reactor Operator License
- RO = NRC Reactor Operator License
- This shift may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of personnel, provided immediate action is taken to restore the shift makeup to within the minimumiequirements.
- A unit is considemd to be operating when it is in a mode other than cold shutdown or refueling shutdown.
4 Unit 1 - Amendment No.490190 15.6.2-3 Unit 2.- Amendment No.-tN 195
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.15.6.2.3 DELETED -
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Unit 1 - Amendment No.-M8190 15.6.2-4 l
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- Unit 2 - Amendment No.-ee.195,
15.6.3.3 In the event the position of Health Physicist is vacated and the proposed replacement does not meet all the qualifications of 15.6.3.2, but is determined to be otherwise well qualified, the concurrence of NRC shall be sought in approving the qualification of that individual.
15.6.3.4 The Shift Technical Advisor shall have a bachelor's' degree or equivalent in a scientific l
or engineering discipline with specific training in plant design and response and analysis of the plant for transients and accidents. The Shift Technical Advisor shall l
also receive training in plant design and layout including the capabilities of instrumentation an4 controls in the control room.
The Operations Manager shall:
15.6.3.5 1)
Hold a Senior Reactor Operator license at PBNP; or 2)
Have held a Senior Reactor Operator license at PBNP or a similar unit; or 3)
Have been certified at an appropriate simulator for equivalent senior operator knowledge level.
If the Operations Manager does not hold a Senior Reactor Operator license at PBNP, then an operations middle manager to whom the operating crews report shall hold a Senior Reactor Operator license at PBNP.
Unit 1 - Amendment No.169,190 15.6.3-2 Unit 2 - Amendment No.ifh7.195 1
15.6.4 TRAINING 15.6.4.1 A retraining and replacement training program fn the facility staff shall'oe maintained under the direction of the Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.
15.6.5 REVIEW AND AUDIT 15.6.5.1 Manager's Supervisory Staff-DELETED (Relocated to owner controlled j
documents)
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i Unit 1 - Amendment No.MS,190 15.6.5-1 Unit 2 - Amendment No.M9,195
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15.6.6 DELETED 3
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1 Unit l'- Amend.nent No.497.190 Um't 2 - Amendment No.-tet.195 15.6.6-1
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15.6.8 PLANT OPERATING PROCEDURES 15.6.8.1 The plant shall be operated and maintained in accordance with approved procedures. Procedures shall be provided for the following operations where these operations involve nuclear safety of the plant:
1.
Normal sequences of stanup, operation and shutdown of components, systems and overall plant.
- 2. Refueling.
- 3. Specific and foreseen potential malfunctions of systems or components including abnormal reactivity changes.
4.
Security Plan implementation.
- 5. Emergencies which could involve release of radioactivity.
6.-
Nuclear core testing.
7.
Surveillance and testing of safety related equipment.
- 8. Fire protection implementation.
15.6.8.2 Approval of Procedures.
A. Each procedure, or change thereto, of the categories listed in 15.6.8.1 (except 15.6.8.1.4) and 15.6.11 shall be reviewed by an individual orl group other than the individual who prepared the procedure, or change thereto.
All p'rocedures of the categories listed in 15.6.8.1 (except 15.6.8.1.4) and l
15.6.11, and modifications to the intent thereof, shall be approved by the Plant Manager or a depanment manager assigned responsibility for those procedures (hereafter referred to as the Approval Authority) prior to implementation. Non-intent changes shall be reviewed and approved in accordance with 15.6.8.2 or 15.6.8.3.
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B. Individuals responsible for reviews in accordance with 15.6.8.2 and 15.6.8.3 shall be members of the plant staff previously designated by the Plant Manager and meet or exceed the_ qualifications of Technical l
Specification 15.6.3.
Unit 1 - Amendment No.-9t,190 15.6.8-1 Unit 2 - Amendment No. 95,195 1
15.6.8 PLANT OPERATING PROCEDURES (Continued)
C. Each review shall include a determination of whether or not additional, cross-disciplinary review is necess.ary. If deemed necessary, such review shall be performed by qualified personnel of the appropriate discipline.
D. Each review shallinclude an assessment for applicability of 10 CFR 50.59 and when necessary appropriate evaluations shall be performed.
15.6.8.3 Changes to Procedures A. Changes to procedures, of the categories in 15.6.8.2A, that may involve a change to the intent of the original procedures shall be approved in accordance with 15.6.8.2.
B. Temporary changes to procedures, of the categories listed in 15.6.8.2A, which do not change the intent of the approved procedure, may b: made provided such changes are approved by two members of the plant staff, at least one of whom holds a Senior Reactor Operator's License.
C. All temporary changes to procedures of the categories listed in 15.6.8.2A shall subsequently be reviewed and approved in accordance with 15.6.8.2 within 2 weeks. Temporary changes only become permanent changes after approval by the Approval Authority.
I Unit 1 -' Amendment No. 9t,190 15.6.8-2 Unit 2 - Amendment No. 95,195
[1 15.7.8 ADMINISTRATTVE CONTROLS 15.7.8.1
-DELETED
. 15.7.8.2 Anghis
- A.
An audit of the activities encompassed by the Radioactive Emuent and Materials Control and Accountability Program (REMCAP), [the Offsite Dose Calculation Manual (ODCM), the Radiological Emuent Control Program (RECP), the Radiological Environmental Monitoring Program (REMP), and the Process Control Program (PCP)] and its implementing procedures shall be performed utilizing either offsite licensee personnel or a consulting firm.
B.
The results of the audit above shall be transmitted to the Chief Nuclear Omcer and the Chairman of the Offsite Review Committee.
15.7.8.3 Plant Oneratins Procedures and Pronrams The Radioactive Emuent and Materials Control and Accountability Program (REMCAP) shall be established, implemented, and maintained in accordance with the provisions of Technical Specification 15.6.8. REMCAP sh4 assure that radioactive emuent and waste material from PBNP complies with applicable Federal, State, and burial ground regulations while keeping all exposures to members of the public as low as reasonably achievable (ALARA). *!his program shall conform to and implement the requirements of PBNP GDC 70 and of 10 CFR 50.34a and 10 CFR 50.36a for the control of radioactive emuents while maintaining doses from these effluents ALARA, shall implement the requirements of 10 CFR 50.34a ani
. General Design Criterion 60 of Appendix A to 10 CFR 50 to suitably control the release and the processing of waste matenals, shall conform to the guidance of Appendix I to 10 CFR 50 and PBNP GDC 17 for the assessment of radioactivity in the environs of PBNP, and shall include remedial actions to be taken whenever the program limits are exceeded REMCAP shall be implemented and maintained under the procedures and methodologies specified in the four (4) manuals / programs listed below and supported, as required, by other procedures. -
Emuent and environmental monitoring shall be addressed in the Quality Assurance Program.
Unit 1 - Amendment Noqq,190 15.7.8-1 Unit 2 - Amendment No.448.,.' 195
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3.
Revisions shall become effective after the approval of the Plant Manager.
B.
Revisions to the EM, ODCM, RECM and REMCAP 1.
Revisions to the EM, ODCM, RECM and REMCAP shall be documented and reviews performed of the revision shall be retaitwd as required in 15.7.8.6. 'Ihe documentation shall contain:
a.
Sufficient information to support the change together with the appropriate analyses or evaluationsjustifying the revision, and b.
A determination that the change will maintain the levels of radioactive effluent control required pursuant to 10 CFR 20.1302, 10 CFR 50.36a, Appendix I to 10 CFR 50, and 40 CFR 190.
2.
Shall become effective after the approval of the Plant Manag 3.
Shall be submitted to the Commission in the form of a complete, legible copy of the entire manual either as part of, or concurrent with, the Annual Monitoring Report for the period of the report in which the revision was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed.
Each copy shall indicate the date (e.g., month / year) the revision was implemented.
4.
In addition to items 1 3 above, all changes regarding explosive gas must be made via the 50.59 process.
i Unit 1 - Amendment No-446 _190 15.7.8-7 Unit 2 - Amendment No. 166, 195
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